ML20084M419

Monthly Operating Rept for Mar 1983

ML20084M419
Person / Time
Site:	Pilgrim
Issue date:	04/13/1983
From:	Harrington W, Whitney G BOSTON EDISON CO.
To:
References
83-90, NUDOCS 8306020154
Download: ML20084M419 (7)

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OPERATI$G DATA REPORT ,

DOCKET NO. 50-293 -

DATE 04/ /83 COMPLETED BY G.G. Whitney TELEPHONE 617-746-7900 u

OPERATING STATUS Pilgrim 1 Notes

l. Unit Name:

March, 1983

2. Reporting Period:

1998. >

3. LicensedThermalPower(MWt): *

4. Nameplate Rating (Gross MWe): 678.

' 5. Design Electrical Rating (Net MWe): 655. ,

6. Maximum Dependable Capacity (Gross MWe): 690.

7. Maximum Dependable Capacity (Net MWe): 670.

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

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9. Power Level To Which Restricted,if Any (Net MWe): None

10. Reasons For Restrictions.If Any:

N/A

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This Monta Yr..to.Date Cumuldve

11. Hours In Reporting Period 744.0 2160.0 90360.0 ,

12. Number Of Hours Reactor Was Critical 744.0 2118.9 64064.2

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13. Reacter Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line

- 744.0 2111.8 61991.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1450560.0 4107840.0 106821432.0 '.

17. Gross Electrical Energy Generated (MWH) 504000.0 __,

1432710.0 35759534.0

18. Net Electrical Energy Generated (MWH) 485066.0 1378843.0 34360354.0

19. Unit Service Factor 100.0 97.8 68.6 ,

20. Unit Availability Factor '00.0 1 97.8 68.6

21. Unit Capacity Factor (Using MDC Net) - 97.3 95.3~ 56.8

22. Unit Capacity Factor (Using DER Net) 99.5 97.5 58.1

23. Unit Forced Outage Rate 0.0 2.2 9.5

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each1:

Refuel Outage to commence January 1984.

25. If Shut Down At End Of Report Period. Estimated Date ot'Startup: Unit Operating s

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8306020154 830413 DR ADOCK 05000 g77)

AVExAGE DAILY UNIT POWER !JEVEL DOCKET NO. 50-293 6

UNIT Pilcrim 1 DATE 04/ /83 COMP! ETED BY G G- N kav IILEPHONE 617-746-7900 March, 1983 MONTH

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, DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe. Net) 1 666. 17 665.

2 666. 13~ 666.

3 666. 39 gg, 4 666. 20 a60 5 479. _

21 6As 6 641. n ggs 664. 664.

7 23 3

665. 2h h6s.

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666. 25

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'!O 665. 26 ccc 665. 7 664.

31 g 666. 3 664.

663. 29 665.

13 666. 30 663.

14 15 666. 31 66s.

16 665.

s INSTRUCTIONS -

On this format. list the average daHy tmit power level in MWe. Net for each t.sy in the reporting month. Compute to the nearest whole megawatt.

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DOCKET NO. 50-293

, UNIT SilUTl) OWNS ANI) POWER REI)UC110NS Pilcrim 1 UNIT NAME 11 ATE 04/ /'83

, COMPLETED gy G.C. Whitnev March, 1983 I

REPORT MONTil TELErilONE 617-746-7900_

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• reg EE 3 Licensee Et t, Cause & Corrective j No. 172te k l-jg oE E

% )Y> yM Event Report #

{y mo g u

3 Actitm to Prevent Recurrence 9 j ;?, g 6

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3 83/03/05 S 0.0 H 5 NA HC HTEXCH Main Condenser backwash p 4 83/03/20 S 0.0 H 5 NA, HC HTEXCH Main Condenser backwash h

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< l 2 3 4 1'

F: Fmced Reason: Metheil: Exhibit G . instructitms .

S: Schedtded A Equipment Failure (Explain) 1-Manual for Preperathm of Data

<t B Maintenance of Test 2-Manual Scram. Entry Sheets for I.icensee ji C-Refueling 3-Autimistic Scram. Event ReporI (LER) File INUREG.,,

j , D-Reguistory Restriction 44)ther (Explain) 0161)

E-Operator Training & License Emandnation 5-Power Reduction F Administrative 5

-l G4)perstional Ersur (Explain) Exhibit I- Same Source

{! 19l77) 11 O her (Explain) 16 I

._. J REFUELING INFORMATION l l

The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo dated January 18, 1978:

For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.

1. The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293.

2. Scheduled date for next Refueling Shutdown: January, 1984

3. Scheduled date for restart following refueling: April, 1984 4.

5. Due to their similarity, requests 4, 5, & 6 are responded to collectively:

6. The fuel, which had been loaded during the 1981 scheduled refueling outage, is of the same P8x8R des 1_gn, as loaded the previous outage con-sisting of 112 P8DRB282 assemblies and 60 P8DRB265 assemblies.

7. (a) There are 580 fuel assemblies in the core.

(b) There are 936 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies.

The actual spent fuel storage capacity is 1770 fuel assemblies at present.

(b) The planned spent fuel storage capacity is 2320 fuel assemblies.

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 834 fuel assemblies.

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PILGRIM NUCLEAR POWER STATION Month MARCH,1983 MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT RECURRENCE ASSOCIATED LER Drywell C-19 Predictive' Degrading Replaced Tube Normal PM tube adjustment LER to be issued leakage maintenance P.M. Tube Performed voltage aging detection plateau HPCI MOV2301-3 Breaker tripped stem bind- Relieve tight N/A N/A ing packing SBLC Standby Lo alarm in setpoint ' reset alarm and Alarm unit checked during N/A liquid Hi/Lo drift corrected set- OPER 9 (operation's tour a,larm ting ,

surveillance)

RCIC A0 1301-50 Steam leak Wear Re-injected Revork valve during refuel N/A Furmanite outage RBCCW P202B(reactor Predictive Mormal wear Disassembled None - Continue to monitor N/A bldg. cooling pump, drained oil pumps condition, routine water pump cleaned all parts maintenance Replaced mech.

seal 5 reasennb1( d i

filled with 797 oil.

RBCCW P202 A (reacto c Stripped lack of replaced coupling Isolated failure N/A ,

b1dg. cooling coupling

• grease water pump)

I6C ATWS Trip lights on Design Performed re- Trip lights that came on have 83 -012 /03L-0  :

system not in- problem vised 8.M.2-29 been' determined not to be a  !

operable -

problem. 8.M'.2-29 has been re--  !

written to verify correct {'

s contact closure to address

, the design problem in the lighting circuit i

Diesel X-107B (emer- Increased con- Cylinder Replaced cylinder Expected degradation for N/A generator gency diesel sumption of anti- head head diesel engines. Predictive generator) freeze. Engine leak maintenance addressed, not inoperable

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PILGRIM NUCLEAR POWER STATION' OPERATIONAL

SUMMARY

FOR MARCH, 1983 The station operated at. essentially 100% (97.3 actual) for.the entire month because of a Safety / Relief valve simmer margin restriction of 1030 psi reactor pressure.

PNPS operated at full load until 3/5/83 when power was reduced to 50%

for condenser backwash and control rod pattern changes. The unit was returned to power later that day and continued at 100% until 3/13/83 when control rod exercises required a 90% power level. On 3/9/83 various minor steam leaks in the HPCI system were repaired, the system being returned to service on 3/10/83. ATWS divi 91on two'was-taken out of service to investigate on apparent problem with the contact status indicator lights. (Ref. LER

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83-012/03L-0). On 3/14/83, the "B" diesel engine was removed from service to repair a water leak and declared operable on 3/16/83 on_3/20/83,'the unit output was reduced to 50%.to heat treat the condenser and backwash ~the system and returned to fullfallowable power early the following day. Control' rods were exercised during the scheduled power reduction. Hypochlorinating

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for slime control in the main-condenser was started on'3/25/83.

A 10% power reduction was taken on 3/27/83 for control rod exercise's and:

a return.to full allowable power the same day.

Safety / Relief Valve Challenges for the Month of March, 1983 Requirement: T.A.P. II.K.3.3 No Safety / Relief valve challenges occurred during the month.

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L BOSTON EDISON COMPANY 800 BOYLSTON STREET BOSTON, MAsSADHUSETTS D2199 WILLIAM D. HARRINGTON April 13,1983 a....v... ........,

asMCL.A.

BECo Ltr. //83- 90 Director Office of Management Information and Program Control U. S.' Nuclear Regulatory Commission Washington, D.C. 20555 Docket Number 50-293 License DPR-35

Subject:

March, 1983 Monthly Report

Dear Sir:

In accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning.

t Respectfully submitted, GGW:em cc: Regional Administrator, Region i U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Standard BECo Distribution CAM I I

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